ML20084Q819
| ML20084Q819 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/01/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20084Q821 | List: |
| References | |
| DPR-22-A-024 NUDOCS 8405210506 | |
| Download: ML20084Q819 (7) | |
Text
- )g IJNITED STATES y'
g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
~ %,r NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated September 10, 1982, as revised on July 29, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the publi:: and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 24 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
FOR THE NilCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing 4
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Attachment:
Changes to the Technical Specifications Date of Issuance:
May 1,1984 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 24 s
FACILITY'OPEJATING LICENSE NO. DPR-22 DOCKET NO. 50-263 i
1 Replace t'he following paces of the Apperdix " " Technical Specifications with the encicSed pages. The revised pages are identified by Amendment number and contain've.tical lines indicating the area of change.
Remove Insert i
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l TA3L5 CF C0 m !:*S Pare 1.0 OETIN!!!035 1
2.0 SATITY LIMITS AND LDtITING SATIM SYS!!M SI-"INGS 6
2.1 and 2.3 Fuel Cladding In=egrity 6
2.1 Bases 10 2.3 3ases 14 2.2 and 2.4 Reactor Coolant System 21 2.2 Bases 22 2.A Bases 24 3.0 LIMITI'O CO:."JIn0NS FOR OPERATION AND 4.0 SURVIILLA?:CI REQUIRE:!INTS 26 3.1 and 4.1 Reactor Procaccion System 26 3.1 3ases 35 4.1 Eases 41 3.2 and L.2 7roces:1ve Inscr==enca: ion 45 A.
Primary Contai:tzene Tsolation Tune: ions 45
' 3.
Emergency-Cove.. Cooling Subsyscess..Actuacion 46 C.
Control Rod 31ocir.Actuacion 46 D.
Deleted I.
Reactor 3uilding Ventilation Isolation and Scandby Gas Treatment System I:1:iation 47 7.
Recirculation 7 ump Trip Ini:iation 48 G.
Safeguards 3us Voltage ? ocac: ton 48 3.2 Bases 6A 4.1 3ases 72 3.3 and 4.3 Control Red System 76 A.
Rese:ivity L1=ications 76 3.
Control Rod '.Jithdrav41 77 C.
Scram Insertion T1=es 31 D.
Control Rod Ac =sulacers 32 I.
Reac:1vi:7 Aacmalies 33 T.
Scran Discharge 7elu=a 33A l
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Required Ac:1on 83A 3.3 and 4.3 34ses 34 L
l Ameiidinent No. 24
1.0 B.iHITING CONDITIONS FOR OPERATION 4.0 SURVEII.I.ANCE RD}UIREHENTS E.
Reactivity Anomalies E.
Reactivity Anomalias At a specific steady state lease condition During the startup test program and at of the reactor actual control rod inventory will be periodically compared to a normal-each startup following refueling outages, alie actual tod inventory shall lee com-taiil computed predict ion of the inventory.
' pared to a normalized computed prediction if the difference esceeds one per cent, delta k, of the inventory. These comparisons w!!!
s eac tor pouer oper-ton shall not be pc.-
be used as base data for reactivity mou-mit ted until alie do=
has been evaluated itoring during subsequent power operation and appropriate coe. u itva action has leecu throughout the fuel cycle. At specific rompleted, power operating conditions, alie actual tod conilguration will lie compared to the configuration expected based upon appropriately corrected past data. Tla te compartann will be made at least every equiv-ent full power aw2 nth.
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3.0 I.IMITING CONDITONS FOR OPERATION 4.0 SURVELLLANCE REQUIREMEKIS
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Scram Dischdrge Volume
- 1. Ihsring reactor operation, the scram discharge The scram discharge volume vent and drain volume vent and drain valves shall be valves shall be cycled quarterly.
operable, except as.specified below.
once per operating cycle verify the 2.
If any scram discharge volume vent or drain scram dischstge volume vent and drain valve is made or found inoperable, the valves close within 30 seconds after integrity of the scram discharge vok an receipt of a reactor scram signal and shall be maintained by either:
open uhen the scram is reset, a.
Verifying daily, for a period not to exceed 7 days, the operability of the redundant valve (s), or
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- b. Haintaining the inoperable valve (s), or the associated redundant valve (s), in the closed posit ion.
Periodically the inoperable and the redundant valve (s) may both he in the open position to allow i
draining the scram discharge volume.
If a or h above cannot be met, at least all but one operable control rods (not including rods removed per specification 3.10.E or Inoperable rods allowed by 3.3.A.2) shall be fully inserted within ten hours.
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Itequi red Action m
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1 If Specifications 3.3.A through D above are not met, an orderly shutdown shall be initiated and have reactor in the cold shutdoun condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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R ses continued 3.3 and 4.3:
3 Deviations beyond tiils magnitude would niot be expected and would require thorougli evaluations.
One per cent roactivity limit is considered safe educe an insertion of this reactivity into
'j the core would not lead to transients exceeding design conditions of the reactor systems.
i As was noted above reactivity anomalies can be found by comparison of the actual control rod inventory to the predicted inventory at a selected base condition. For esemple, the predicted control rod' inventory at 1001 power at a specified point in time can be compared to the actual enntrol rod inventory at 1001 power and at the specified time to determine if a reactivity anomaly exista. Tlie Honticello Plant lies been designed to increase or decrease power level i
as t,he system load demand changes. For this type of plant an equilibrium condition of time variables importent to making a control rod inventory pr.ediction, specifically tiie reactivity g
l effects of the xenon, is rarely achieved. The uncertatuties of calculating the control. rod laiventory wille non-equilibrium menon conditions can result in errors which can be misconstrued as reactivity anomalies. Therefore, this specification calla for performing of rod inventory comparisons at a time when menon will not be a source of error.
F. The aa'ety function of the scram discharge volume vent and drain valves is to limit the loss of reactor coolesc leaked past the CRD seals while the scram va)ves are open. To accomplish this, the vent and desin valves must either be in the closed position or close in a timely manner upon scram initiation. The closure time of 30 seconds is based on a letter dated July 25, 1980 to J G Keppler (Region III) from D E Gilberts (HSP) concerning IE Bulletin No. 80-14.
Redundant isolation valves have been provided for each vent and drain line. Closure of one of the valves in each line would be sufficient to maintain the integrity of the scram discharge volume, i
C.
Whenever a specification (or specifications) can not be met for a particular mode of operation, the reactor would be placed 13 a mode for which the specification (or specifications) are not required. This requires immediate initiation of a reactor shutdown upon discovery that specif-ications 1.3A through 3.3D are not met.
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